ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
David A. Mandell
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 383-392
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32712
Articles are hosted by Taylor and Francis Online.
To calculate the radiative heat transfer between fuel bundle surfaces and from the surfaces to the vapor and droplets in a boiling water reactor, it is necessary to calculate the geometrical fuel factors. These view factors, which are the fraction of energy leaving one surface that reaches a second surface when no fluid exists, must be calculated for every pair of fuel rods, from every rod to every channel segment, and from one channel segment to a second channel segment. The crossed-string method was used to obtain algebraic equations for the view factors between rods of the same diameter, from rods-to-channel segments, and from one channel segment to a second channel segment. These equations can be easily incorporated into computer codes. Conservation of energy was used to verify the view factor equations.